Shipboard Cobalt-60 Radiopasteurizer for Marine Products (open access)

Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
System: The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963 (open access)

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
System: The UNT Digital Library
Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices (open access)

Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices

Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date: June 30, 1963
Creator: Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
System: The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 1, Experimental Apparatus and Results of Initial Tests and Analysis (open access)

Boiling Studies for Sodium Reactor Safety: Part 1, Experimental Apparatus and Results of Initial Tests and Analysis

Abstract: An experimental and analytical research program is described which is designed to meet certain specific needs for data and methods required to make improved predictions of transient voids, burnout, flow, and fuel temperature during extreme accidents in sodium-cooled reactors.
Date: August 30, 1963
Creator: Noyes, R. C.
System: The UNT Digital Library
EDP Procedures in Technical Library Operations (open access)

EDP Procedures in Technical Library Operations

Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date: July 30, 1963
Creator: Griffin, Hillis L.
System: The UNT Digital Library
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes (open access)

The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date: July 30, 1963
Creator: Pessl, H. J.
System: The UNT Digital Library